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Untersuchungen zur Abtrennung von Iod-129 aus dem Filtermaterial AC 6120 im Hinblick auf eine zukünftige Transmutation



1995
Forschungszentrum Jülich GmbH Zentralbibliothek, Verlag Jülich

Jülich : Forschungszentrum Jülich GmbH Zentralbibliothek, Verlag, Jül-3119 ()

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Report No.: JUEL-3119

Abstract: Future transmutation of some selected long-lived radionuclides into short-lived and stable nuclides could drastically reduce the long-term radiotoxicity of radioactive waste. However, this will require further development of the reprocessing technology with the aim of a loss-free separation of the radionuclides to be transformed. In addition to several minor actinides the long-lived fission product I-129 is of the greatest relevance for future transmutation. This study first describes the behaviour and distribution of I-129 in the fue1 cyle. According to the present state of the art in reprocessing technology, the I-129 contained in spent fuel elements can be completely transferred into the dissolver off-gas and efficiently adsorbed on silver-nitrate-impregnated silica (AC 6120). For future transmutation, the I-129 should again be separated selectively and as completely as possible from the AC 6120 adsorption matrix. Experimental studies show that a quantitative recovery (> 99 %) of the iodine is possible by simple chemical processes /56/. The resultant possibilities of producing a target for transmutation are being discussed.

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Note: Record converted from JUWEL: 18.07.2013

Contributing Institute(s):
  1. Institut für Sicherheitsforschung und Reaktortechnik (ISR)

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 Record created 2013-07-18, last modified 2020-06-10


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